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[null,"1.","Record Nr.",null,"UNINA9910962557803321"]
[null,null,"Titolo",null,"Application of stable lead isotope Pb-208 in nuclear power engineering and its acquisition techniques / / Georgy Levanovich Khorasanov, editor"]
[null,null,"Pubbl/distr/stampa",null,"New York., : Nova Publishers, c2013"]
[null,null,"ISBN",null,"1-62417-661-5"]
[null,null,"Edizione",null,"[1st ed.]"]
[null,null,"Descrizione fisica",null,"1 online resource (196 p.)"]
[null,null,"Collana",null,"Nuclear materials and disaster research"]
[null,null,"Disciplina",null,"621.48/33"]
[null,null,"Soggetti",null,"Nuclear engineering - Materials"]
[{"$nulls":4},"Nuclear power plants - Materials"]
[{"$nulls":4},"Lead - Isotopes"]
[null,null,"Lingua di pubblicazione",null,"Inglese"]
[null,null,"Formato",null,"Materiale a stampa"]
[null,null,null,"Livello bibliografico","Monografia"]
[null,null,null,"Note generali","Description based upon print version of record."]
[null,null,null,"Nota di bibliografia","Includes bibliographical references and index."]
[null,null,"Nota di contenuto",null,"Intro -- APPLICATION OF STABLE LEAD ISOTOPE PB-208 IN NUCLEAR POWER ENGINEERING AND ITS ACQUISITION TECHNIQUES -- APPLICATION OF STABLE LEAD ISOTOPE PB-208 IN NUCLEAR POWER ENGINEERING AND ITS ACQUISITION TECHNIQUES -- CONTENTS -- PREFACE -- SOME ADVANTAGES IN USING LEAD-208AS COOLANT FOR FAST REACTORS AND ACCELERATOR DRIVEN SYSTEMS -- ABSTRACT -- INTRODUCTION -- 1. SMALL NEUTRON ABSORPTION IN FR AND ADS COOLANT FROM LEAD-208 -- 2. GAIN IN CORE FUEL LOADING DUE TO EXCESS  OF NEUTRONS -- 3. INCREASING THE FUEL BREEDING GAIN IN FRS  AND ADSS COOLED WITH LEAD-208 -- 4. HARDENING OF ADS AND FR NEUTRON  SPECTRA IN USING LEAD-208 INSTEAD  OF NATURAL LEAD OR LEAD-BISMUTH -- CONCLUSION -- ACKNOWLEDGMENTS -- REFERENCES -- INTRODUCTIONS OF 208PB COOLANT  TO INNOVATIVE FAST REACTORS -- ABSTRACT -- INTRODUCTION -- Requirements Imposed on Nuclear Energy Utilization -- CANDLE Reactor -- How Does CANDLE Reactor Satisfy the Requirements  on Nuclear Energy Utilization? -- TECHNIQUES INTRODUCED TO CANDLE REACTOR -- 208PB COOLANT -- Lead and Lead Bismuth -- 208PB COOLANT -- 208PB COOLED CANDEL REACTORS -- Middle Sized Reactor -- POWER FLATTENING -- SMALL LONG-LIFE REACTOR -- REFERENCES -- RADIOGENIC LEAD WITH DOMINANT CONTENT OF 208PB: NEW COOLANT, NEUTRON MODERATOR AND REFLECTOR FOR INNOVATIVE NUCLEAR FACILITIES -- ABSTRACT -- INTRODUCTION -- I. NEUTRON-"]
[{"$nulls":4},"PHYSICAL PROPERTIES AND ADVANTAGES OF RADIOGENIC LEAD -- II. ADVANTAGES FROM APPLICATIONS OF IN FAST REACTORS 208 PB -- II.A. Improvement of the Reactor Safety. Coolant Temperature Reactivity Coefficient -- II.B. Prompt Neutron Lifetime 20 -- II.B.1. One-Dimentional Axial Model of Reactor -- II.B.2. Reactor Kinetics -- II.B.3. One-Dimentional Axial Model of the Fast Reactor Brest* with Thick Reflector -- II.B.4. Spherical Model of the Fast Reactor Brest* with Thick Reflector."]
[{"$nulls":4},"II.B.5. Impact of Reflector Parameters on Fission Distribution and Neutron Spectrum -- II.C. Models of Neutron Kinetics in the Fast Reactor Brest*  with Thick Reflector -- II.C.1. One-Point Model -- II.C.2. Multi-Point Model -- II.C.3. Neutron Kinetics of the Fast Reactor Brest* with Thick Pb Reflector 208 -- III. ENHANCED PROLIFERATION RESISTANCE OF PU-CONTAINING FUEL -- IV. THERMAL-HYDRAULIC ADVANTAGES  OF THE REACTOR CORE COOLED BY 208Pb as a coolPB -- V. REPLACEMENT OF NITRIDE BY OXIDE  URANIUM-PLUTONIUM FUEL -- VI. POTENTIAL FOR FUEL BREEDING IN AXIAL  URANIUM BLANKETS -- VII. ADVANTAGES FROM APPLICATION  OF 208PB IN ADS-SYSTEMS -- VII.A. High Neutron Flux in an ADS Blanken -- VII.B. Transmutation in Resonance Range of Neutron Energy -- VII.C. High-Flux ADS with Cooled Transmutation Zone -- VIII. NATURAL RESOURCES OF RADIOGENIC LEAD -- CONCLUSION -- REFERENCES -- PHOTOCHEMICAL LASER SEPARATION  OF LEAD ISOTOPES FOR SAFE NUCLEAR POWER REACTORS -- ABSTRACT -- 1. INTRODUCTION -- 2. METHODS OF LASER ISOTOPE SEPARATION -- 3. SELECTIVE EXCITATION OF THE METASTABLE  LEVELS OF LEAD -- 4. EXPERIMENTAL AND APPROACH -- 5. RESULTS AND DISCUSSION -- CONCLUSION -- REFERENCES -- ASSESSMENT OF SPECIFIC COST OF HIGHLY ENRICHED LEAD-208 ISOTOPE BY GAS CENTRIFUGES USING VARIOUS  RAW MATERIALS -- ABSTRACT -- DESIGNATION -- INTRODUCTION -- THEORETICAL BACKGROUND -- DISCUSSION -- Enrichment from the Natural Lead Isotope Mixture -- Enrichment from the Radiogenic Lead -- CONCLUSION -- REFERENCES -- METHOD FOR OBTAINING ISOTOPICALLY ENRICHED METAL LEAD  FROM MONOISOTOPIC TETRAMETHYLLEAD AND ITS PURIFICATION -- ABSTRACT -- 1. INTRODUCTION -- 2. SYNTHESIS OF PB(CH3)4 -- 3. CONVERSION OF ISOTOPE-ENRICHED PBTO METALLIC LEAD 208(CH3)4 -- 4. PURIFICATION OF ISOTOPICALLY ENRICHED METALLIC LEAD -- CONCLUSION -- REFERENCES -- INDEX."]
[null,null,null,"Sommario/riassunto","The book provides an overview of the advantages in using lead enriched with stable lead isotope lead-208 instead of natural lead as a coolant of fast reactors (FRs) and accelerator driven systems (ADS). Lead-208 as a twice magic nucleus has low cross sections of neutron radiation capture and small moderation of neutrons in the range of neutron energies 10 eV 20 MeV, i.e. in FR and ADS core neutron spectra. These unique features of lead-208 lead to the economy of neutrons, hardening the neutron spectra and other profitable factors."]